Heterogeneous core designs and thorium based fuels for heavy water reactors

ABSTRACT

A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissile fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided.

INCORPORATION BY REFERENCE TO ANY PRIORITY APPLICATIONS

Any and all applications for which a foreign or domestic priority claimis identified in the Application Data Sheet as filed with the presentapplication are hereby incorporated by reference under 37 CFR 1.57.

This application is a divisional of U.S. application Ser. No.14/154,633, filed Jan. 14, 2014, which in turn claims priority to andthe benefit of U.S. provisional application 61/753,851, entitledHETEROGENEOUS CORE DESIGNS AND THORIUM BASED FUELS FOR HEAVY WATERREACTORS, and filed Jan. 17, 2013. The entire contents of all priorityapplications are hereby incorporated by reference.

BACKGROUND Field

The invention relates to core designs for thorium based fuels for heavywater reactors and more specifically to heterogeneous core designs forthorium based seed fuel and blanket fuel for channel-type heavy waterreactors as well as thorium based fuel bundles for a heterogeneous coredesign.

Description of the Related Art

Research into the use of thorium as a new primary energy source hasrecently been explored. Thorium-232 (Th-232) is a naturally occurringisotope and is substantially more abundant than uranium. Although notfissile, upon absorbing a neutron will transmute to uranium-233 (U-233),which is an excellent fissile fuel material. Thorium fuel conceptstherefore require that Th-232 is first irradiated in a reactor toprovide the necessary neutron dosing. The U-233 that is produced caneither be chemically separated from the parent thorium fuel and recycledinto new fuel, or the U-233 may be usable in-situ in the same fuel form.

Thorium fuels therefore require a fissile material as a driver so that achain reaction (and thus supply of surplus neutrons) may be maintained.Fissile driver options are U-233, U-235 or Pu-239.

It is possible, although difficult, to design thorium fuels that producemore U-233 in thermal reactors than the fissile material they consume(this is referred to as having a fissile conversion ratio of more than1.0 and is also called breeding). Thermal breeding with thorium ispossible using U-233 as the fissile driver, and to achieve this theneutron economy in the reactor has to be very good (i.e., low neutronloss through escape or parasitic absorption). The possibility to breedfissile material in slow neutron systems is a unique feature forthorium-based fuels.

Another distinct option for using thorium is as a ‘fertile matrix’ forfuels containing transuranic elements such as plutonium. No newplutonium is produced from the thorium component, unlike for uraniumfuels, and so the level of net consumption of this metal is rather high.

In fresh thorium fuel, all of the fissions (thus power and neutrons)derive from the driver component. As the fuel operates the U-233 contentgradually increases and it contributes more and more to the power outputof the fuel. The ultimate energy output from U-233, and hence indirectlythorium, depends on numerous fuel design parameters, including: fuelburnup attained, fuel arrangement, neutron energy spectrum and neutronflux. The fission of a U-233 nucleus releases about the same amount ofenergy (200 MeV) as that of U-235.

An important principle in the design of thorium fuel is that of fuelarrangements in which a high fissile (and therefore higher power) fuelzone referred to as the seed region is physically separated from thefertile (low or zero power) thorium part of the fuel referred to as theblanket region. Such an arrangement is far better for supplying surplusneutrons to thorium nuclei so they can convert to fissile U-233.

Previous heavy water reactor core designs and associated fuel forchannel-type heavy water reactors using thorium-based fuels have notbeen able to achieve simultaneously high fuel burnup, high fissileutilization and high conversion ratios, while also meeting design goalsof high core-average power densities, meeting goals of operating limitson bundle power and maximum linear element ratings while keepingreactivity coefficients, such as for example coolant void reactivity,within desired values to enhance safety characteristics.

Previous research in heavy water reactors have tended to focus on thedesign of homogeneous cores and heterogeneous fuel bundle designs thatuse neutron absorbing poisons to reduce void reactivity and hasneglected to consider alternative design options.

A thorium fuel based core design and/or a fuel bundle design thatmitigates one or more various shortcomings is therefore in need.

SUMMARY

Thorium is an attractive fuel option to improve the sustainability ofthe nuclear fuel cycle, given the limited and unevenly distributeduranium reserves. As natural thorium does not contain a fissile isotope,implementation of thorium fuels in a reactor must involve a fissilecomponent, generally either plutonium or uranium. The physicalseparation of a lower fissile blanket fuel and a higher fissile seedfuel into separate adjacent regions in a heterogeneous reactor coreallows for the potential to improve the fissile utilization and increasethe sustainability of the thorium fuel cycle.

In one embodiment of the invention, there is provided a channel typeheterogeneous reactor core for a heavy water reactor for burnup ofthorium based fuel, the heterogeneous reactor core comprising at leastone seed fuel channel region comprising seed fuel channels for receivingseed fuel bundles of thorium based fuel; and at least one blanket fuelchannel region comprising blanket fuel channels for receiving blanketfuel bundles of thorium based fuel; wherein the seed fuel bundles have ahigher percentage content of fissile fuel than the blanket fuel bundles.

In an additional embodiment to that outlined above, the at least oneseed fuel channel region and the at least one blanket fuel channelregion are set out in a checkerboard pattern within the heterogeneousreactor core.

In an additional embodiment to that outlined above, the at least oneseed fuel channel region and the at least one blanket fuel channelregion are set out in an annular pattern within the heterogeneousreactor core.

In an additional embodiment to that outlined above, the seed fuel bundlecomprises 35% or more UO2 and 65% or less ThO2.

In an additional embodiment to that outlined above, the seed fuel bundlecomprises 3% or more PuO2 and 97% or less ThO2.

In an additional embodiment to that outlined above, the blanket fuelbundle comprises 30% or less UO2 and 70% or more ThO2.

In an additional embodiment to that outlined above, the blanket fuelbundle comprises 2% or less PuO2 and 98% or more ThO2.

In another embodiment of the invention, there is provided a fuel bundlefor use in a channel type heterogeneous reactor core of a heavy waterreactor, the fuel bundle comprising a central displacement tube; and aplurality of thorium based fuel pins surrounding the centraldisplacement tube.

In an additional embodiment to that outlined above, the centraldisplacement tube is filled with ZrO2, MgO, BeO, graphite or stagnantD2O coolant.

In an additional embodiment to that outlined above, there are 21radially positioned thorium based fuel pins surrounding the centraldisplacement tube.

In an additional embodiment to that outlined above, there are 35radially positioned thorium based fuel pins surrounding the centraldisplacement tube.

In an additional embodiment to that outlined above, the fuel bundle is aseed fuel bundle and the plurality of thorium based fuel pins comprisesa homogeneous mixture of (PuO2+ThO2) with a PuO2 content of 3% orhigher.

In an additional embodiment to that outlined above, the fuel bundle is aseed fuel bundle and the plurality of thorium based fuel pins comprisesa homogeneous mixture of (UO2+ThO2) with a UO2 content of 35% or higher.

In an additional embodiment to that outlined above, the fuel bundle is ablanket fuel bundle and the plurality of thorium based fuel pinscomprises a homogeneous mixture of (PuO2+ThO2) with a PuO2 content of 2%or less.

In an additional embodiment to that outlined above, the fuel bundle is ablanket fuel bundle and the plurality of thorium based fuel pinscomprises a homogeneous mixture of (UO2+ThO2) with a UO2 content of 30%or less.

In an additional embodiment, the present invention provides for the useof a fuel bundle such as those embodiments outlined above in channeltype heterogeneous reactor core of a heavy water reactor for burnup ofthorium based fuel.

BRIEF DESCRIPTION OF THE DRAWINGS

FIG. 1A-1E show illustrative schematic embodiments of 5 different fuelbundle designs according to the present invention;

FIG. 2 is a schematic illustrative of one embodiment of a heterogeneouscore design for accommodated thorium based seed and blanket fuelbundles;

FIG. 3 is a schematic illustrative of another embodiment of aheterogeneous core design for accommodated thorium based seed andblanket fuel bundles;

FIG. 4 is a schematic illustrative of another embodiment of aheterogeneous core design for accommodated thorium based seed andblanket fuel bundles;

FIG. 5 is a schematic illustrative of another embodiment of aheterogeneous core design for accommodated thorium based seed andblanket fuel bundles;

FIG. 6 is a schematic illustrative of another embodiment of aheterogeneous core design for accommodated thorium based seed andblanket fuel bundles;

FIG. 7 is a schematic illustrative of another embodiment of aheterogeneous core design for accommodated thorium based seed andblanket fuel bundles;

FIG. 8 shows Table 1 relating to Composition of Reactor-Grade Plutonium(RGPu);

FIG. 9 shows Table 2 relating to Isotopic Composition of LEU;

FIG. 10 shows Table 3 relating to a Description of Different LatticesTested;

FIG. 11 shows Table 4 relating to Dimensions of Components for VariousLattices Tested;

FIG. 12 shows Table 5 relating to Fuel Bundle Ring Specifications;

FIG. 13 shows Table 6 relating to Material Specifications For KeyComponents For Various Lattices Tested;

FIG. 14 shows Table 7 relating to Mass Fractions For Elements/IsotopesIn Various Fuel Types For Modified 35-Pu/Th—Zr)2-Rod Fuel Bundles;

FIG. 15 shows Table 8 relating to Performance Characteristics Of VariousSeed/Blanket Fuel Combinations In The 1S-1B Heterogeneous Seed/BlanketCore Design; and

FIG. 16 shows Table 9 relating to Performance Characteristics Of VariousSeed/Blanket Fuel Combinations In The 84% Seed/16% Blanket HeterogeneousSeed/Blanket Core Design.

DETAILED DESCRIPTION

A heterogeneous reactor core for a channel type heavy water reactor isprovided. A channel-type heavy water reactor, similar to what is beingcurrently used in nuclear power generation may be used as the initialbasis for the design. The heterogeneous core comprises a lattice ofchannels for receiving seed or blanket fuel bundles in the channels aswill be discussed below with reference to FIGS. 2-7. The core maycontain from 25% to 84% seed fuel channels while the balance are blanketfuel channels.

The nuclear fuel is in the form of short, (˜50 cm) or longer (>50 cm)fuel bundles made generally with one or two rings of fuel pins. It hasbeen determined that to help minimize coolant void reactivity whilemaximizing fuel burnup and fissile utilization, the fuel bundle isdesigned to have only one or two rings of fuel pins, with a centraldisplacer tube filled with stagnant coolant, or a solid moderator, forexample graphite, or material with a low neutron scattering and lowneutron absorption cross section, for example ZrO₂ or MgO. The fuelbundles will be discussed in more detail below with reference to FIGS.1A-1E.

The nuclear fuel bundles are made from thorium, mixed with eitherplutonium or uranium, generally in oxide, carbine, silicide or ametallic-alloy form.

As depicted in various non-limiting embodiments in FIGS. 2-7, anembodiment of the reactor core of the is a heterogeneous design withphysically separate regions of seed fuel channels and blanket fuelchannels arranged in a lattice. In FIGS. 2-7, seed channels arerepresented by an S and blanket channels are represented by a B. Seedfuel is made with higher concentrations of fissile fuel mixed withthorium and is used primarily to generate power and excess neutrons todrive blanket fuel. The blanket fuel is made with lower concentrationsof fissile fuel mixed with thorium and used primarily to convert fertilethorium fuel into fissile fuel. There is some power generation by theblanket fuel.

A seed channel, in one embodiment, is for seed bundles only while ablanket channel is for blanket bundles only.

In the embodiments shown, each channel of the heterogeneous core has 12bundles (either seed or blanket).

As shown, the core may contain from 25% to 84% seed fuel channels, whilethe balance are blanket fuel channels. The core may have a lattice in acheckerboard-type arrangement of seed and blanket fuel channels such asthose shown in FIGS. 6 and 7. Alternatively, the core may have a latticein an annular arrangement of seed and blanket fuel channel regions withthe outermost ring of the fuel channels adjacent to the radial reflector(not shown) of the core filled with blanket fuel channels such as thoseshown in FIGS. 2, 3, 4 and 5. It will be appreciated that there areseveral different permutations of heterogeneous seed/blanket corelayouts which may be used or implemented and those shown in FIGS. 2 to 7are not intended to be limited but rather illustrative of variousembodiments of the concept of heterogeneous cores of the invention.

The heterogeneous core allows for different and dynamic refuelingstrategies as the blanket fuel regions and the seed fuel regions can berefueled at different rates to achieve desirable burnup levels and corepower distributions. Refueling strategies will be discussed in moredetail below.

The reactor core may be similar to current reactor cores such as theCANDU-6/EC-6 reactor which has 380 fuel channels with a square latticepitch of 28.575 cm. Each channel thereof contains 12 fuel bundles, eachapproximately 50 cm long. Current CANDU cores use a homogeneous core ofnatural uranium (NU). Some more advanced designs use a single type offuel and are still considered homogeneous.

Shown in FIGS. 1A-1E are embodiments of fuel bundles for use in thechannels of the heterogeneous core.

As can be seen in the Figures, the fuel bundles include a centraldisplacer tube to replace the central 8 fuel pins in a 43-elementbundle, leaving outer rings of 14 and 21 fuel pins (FIGS. 1B and 1C). Afurther design, shown in FIGS. 1D and 1E includes a larger centraldisplacer tube to replace the central 22 pins in a 43-element bundleleaving an outer ring of 21 fuel pins. Without wishing to be limited,the central displacer tube may be filled with ZrO2, MgO, BeO, graphiteor stagnant D2O coolant.

The purpose of the central displacer tube is to reduce coolant voidreactivity (CVR). An advantage of the central displacer tube is that ithelps to reduce the CVR, improving the safety characteristics of thelattice and the reactor during a postulated accident scenario, wherethere is a loss of coolant.

The fuel pins of either the 21-element bundle or the 35-element bundlemay be a combination of plutonium and thorium or low enriched uraniumand thorium depending on whether the bundle is for use in a seed fuelregion or blanket fuel region.

In FIG. 1A, the inner 8 fuel pins are all the same, namely ThO2 and theouter 35 fuel pins are all the same, namely a homogeneous mixture of(PuO₂+ThO₂) or (UO₂+ThO₂).

In the fuel bundles shown in FIGS. 1B and 1C, the 35 fuel pins are allthe same, namely a homogeneous mixture of (PuO₂+ThO₂) or (UO₂+ThO₂)wherein the fuel bundle of FIG. 1B has central Zr-4 displacement tubefilled with stagnant D2O coolant and the fuel bundle of FIG. 1C has acentral Zr-4 displacement tube filled with ZrO2.

In the fuel bundles shown in FIGS. 1D and 1E, the 21 fuel pins are allthe same, namely a homogeneous mixture of (PuO₂+ThO₂) or (UO₂+ThO₂)wherein the fuel bundle of FIG. 1D has central Zr-4 displacement tubefilled with stagnant D₂O coolant and the fuel bundle of FIG. 1E has acentral Zr-4 displacement tube filled with ZrO₂.

In the embodiments of fuel bundles wherein PuO₂ is mixed with ThO₂, thePu is “reactor grade” Pu. In embodiments of fuel bundles wherein UO₂ ismixed with ThO₂, then the U is LEU (low enriched uranium), with afissile content of about 5 wt % U-235/U in one non-limiting embodiment.The volume fraction of PuO₂ in (Pu+Th)O₂ may range from 1% to 13% invarious non-limiting embodiments. The volume fraction of UO₂ in (U+Th)O₂may range from 5% to 70% in various non-limiting embodiments.

It will be appreciated that the mixture (volume fractions of either PuO2or UO₂ in (Pu+Th)O₂ or (U+Th)O₂) is dependent on whether the fuel is“seed” or “blanket” fuel. Seed fuel has a higher volume fraction of PuO₂or UO₂ than blanket fuel.

Typically, seed fuel contains fuel with 3% or higher PuO2 in (Pu,Th)O₂,or 35% or higher UO₂ in (U,Th)O₂.

The choice of LEU (in the non-limiting embodiment shown, 5 wt % U-235/U)for mixing with thorium (Th) is generally based on practical andeconomic considerations. 5 wt % U-235/U is readily available fromexisting enrichment facilities throughout the world as is therefore morecommonly used.

The choice of reactor grade Pu (generally about 0.67 wt % fissile Pu(Pu-239+Pu-241)) for mixing with Th is generally based on the assumptionthat most of the Pu inventory available in the world today is found inthe spent fuel from light water reactors (LWRs). It is conceivable thatone might use Pu from other sources, such as spent CANDU reactor naturaluranium fuel, or Magnox reactor natural uranium fuel, or plutoniumobtained from nuclear weapons stockpiles, or from a fast breederreactor. In these other potential sources of plutonium, the fissilecontent will be different, probably higher. In principle, the plutoniumfrom these alternative sources may be used in the heterogeneous reactordesign as well, but given the assumption that the fissile plutoniumcontent is higher, then the volume fraction of PuO₂ in (Pu,Th)O₂ wouldlikely be lower to achieve the same level of burnup.

Generally, a typical seed fuel will contain 35% UO₂ (or more) and 65%ThO₂ (or less), or it will contain 3% PuO₂ (or more) and 97% (or less)of ThO₂. Whereas a typical blanket fuel will contain 30% UO₂ (or less)and 70% ThO2 (or more), or it will contain 2% PuO₂ (or less) and 98% (ormore) of ThO₂.

The fraction of the core's fuel channels that are seed channels canrange from about 25% to about 84%. In most designs, the fraction isapproximately 50% seed fuel channels and 50% blanket fuel channels asshown for example in FIGS. 2, 4 and 7. The core layout shown in FIG. 5includes approximately 84% seed channels (320 channels) and 16% blanketchannels (60 channels).

An advantage of using more seed channels is that one can generate morepower and achieve higher burnup while maintaining core reactivity. Inaddition, by using more seed the reactor may be operated at a higherpower level, with a higher core-average power density.

Typically, most of the previous CANDU core designs involving thoriumbased fuels have assumed a homogeneous core with one fuel type.

The refuelling rates (and the core-average burnup of the fuel) depend onthe choice of the fuel used (its initial enrichment), the desired radialand axial power distribution in the core, and the refuelling scheme. Onerefuelling scheme is a simple two-bundle shift, with bi-directionalfuelling in alternating channels. Bundles are inserted from one side ofthe reactor, and are progressively moved to the other side until theyreach the desired burnup.

The objective in adjusting the exit burnup in each channel (and hencethe refuelling rate) is to ensure that the maximum bundle power staysbelow ˜750 kW, and that the maximum channel power stays below ˜6,500 kW.However, it is also ideal to make the radial and axial powerdistribution as flat as possible, in order to maximize the powergenerated in the core, for economic advantage.

The initial core designs used 35-element Pu/Th seed fuel that wouldachieve an approximate discharge burnup of 20 MWd/kg to 40 MWd/kgburnup. In most of the cases studied that meant using (3 wt % PuO₂/97 wt% ThO₂) for the seed to achieve a burnup of ˜20 MWd/kg. For core-averageburnups closer to 40 MWd/kg, this means using (4 wt % PuO2/96 wt %ThO2). Most of the blanket fuel was either (2 wt % PuO₂/98 wt % ThO₂),burned to ˜20 MWd/kg, or (1 wt % PuO2/99 wt % ThO2) burned to 40 MWd/kg.

Heterogeneous cores with LEU/Th fuel have not been tested yet, but theywould use the same methods that were used in the analysis of the coreswith Pu/Th fuel.

There are two additional refuelling strategies to further improve theperformance of the heterogeneous seed/blanket core, although these havenot yet been tested:

1) To carry out axial shuffling of the fuel bundles in a given channelto help flatten the axial power distribution. This could be particularlyuseful in cores using seed fuel with higher levels of fissile enrichment(such as 5 wt % PuO₂/95 wt % ThO₂) and higher burnups (greater than 40MWd/kg). The use of axial shuffling has been considered in the past byAECL in studies of CANDU reactor cores using SEU fuels (1.2 to 3 wt %U-235/U).

2) To send high enrichment, high-burnup seed fuel through a core twiceor three times, somewhat analogous to what is done with batch refuellingin light water reactors. This is what would be called a 2TT (2 timesthrough thorium) or 3TT (3 times through thorium) fuel cycle.

For example, a seed fuel bundle which is estimated to have enoughreactivity (and initial fissile content) to achieve a large dischargeburnup will go through the CANDU core in three passes in three differentchannels.

In addition, for example, a 35-element bundle might be made of (5 wt %PuO₂/95 wt % ThO₂) and lattice physics calculations indicate that itcould achieve a final burnup of ˜54 MWd/kg. Instead of pushing theburnup of the fuel bundle from 0 to 54 MWd/kg in a single pass throughthe core, it can be divided up into two or three passes through thecore. If divided into 3 passes, then the fuel would be burned from 0 to18 MWd/kg in the first pass in one channel, 18 to 36 MWd/kg in the 2ndpass in another channel, and finally 36 to 54 MWd/kg in the third passthrough another channel. A smaller change in the burnup between theinlet and exit of a given fuel channel will help flatten the axial powerdistribution, and permit a higher core power density, while stayingwithin limits of peak bundle power and peak channel power. This type ofrefuelling scheme combines the on-line, bi-directional, continuousrefuelling features of a CANDU reactor with the multi-batch zonerefuelling schemes of a light water reactor (such as a PWR).

Shown in FIGS. 8 to 16 are Tables 1 to 9 which set out geometryspecifications and material specifications of the different fueldesigns.

Table 1 in FIG. 8 shows an embodiment wherein the reactor gradeplutonium contains ˜52 wt % Pu-239 and ˜15 wt % Pu-241, giving a totalfissile content of ˜67 wt % Pu-fissile/Pu.

Table 2 in FIG. 9 shows the isotopic composition of LEU in oxide form.Thus, the fissile content is ˜5 wt % U-235/U and the balance of uraniumis U-238 and U-234.

Table 3 in FIG. 10 shows a description of different lattices tested.There are 10 different lattice designs, which are differentiated bygeometry (5 geometry types) and fuel type (two fuel types, either(U,Th)O₂ or (Pu,Th)O₂) in the outer 35 or 21 pins. Only bundle designs 1and 6 have 8 central ThO₂ pins. All other pins are a mixture of either(U,Th)O₂ or (Pu,Th)O₂.

Table 4 in FIG. 11 shows the dimensions of components for variouslattices tested. The dimensions are given for a fuel pellet made of(Pu,Th)O₂ or (U,Th)O₂, or ThO₂, the radius of the clad for the fuelelement, the inner and outer radius for the central displacer tube, theinner and outer radius for the pressure tube (PT), the inner and outerradius for the calandria tube (CT).

Table 5 in FIG. 12 shows the number of fuel pins and the pitch circleand radius, and the angular offset for the first fuel pin in the bundle.Note: bundle design 1 a is the only one that has 4 rings of fuel pins(1+7+14+21). Bundle designs 1 b and 1 c do not have a central pin or aninner ring of fuel pins, only two outer rings of fuel pins (14+21).Bundle designs 1 d and 1 e have only a single outer ring of 21 fuelpins.

Table 6 in FIG. 13 shows the material specifications for key componentsfor various lattices tested. The type of material, its nominal operatingtemperature, and its nominal material mass density are given. Thenominal purity of the heavy water moderator and the heavy water coolantare also specified. However, it should be pointed out that the purity ofthe heavy water in both the moderator and the coolant could beincreased.

Table 7 in FIG. 14 shows the value of the mass fractions for Pu-fissile(Pu-239+Pu-241) Pu, Th, and O in (Pu,Th)O₂ for various volume fractionsof PuO₂ in (Pu,Th)O₂. The fuels containing low volume fractions of PuO₂(e.g., 2% or less) are considered blanket fuel, while the fuelscontaining higher volume fractions of PuO2 (e.g. 3% or higher) areconsidered seed fuel.

Also shown below is a sample set of core calculation results for twocores (1S-1B, and 84% Seed/16% Blanket) with different combinations ofSeed and Blanket fuels. The data for the 1S-1B core design is shown inTable 8/FIG. 15. This shows the various performance characteristics of 5different core designs, which differ in the type of seed and blanketfuel used.

The data for the 84%-Seed/16% blanket core design is shown in Table9/FIG. 16. This shows the various performance characteristics of 4different core designs, which differ in the type of seed and blanketfuel used.

The above described heterogeneous reactor core and fuel bundles areintended to be illustrative of the invention and are not intended to belimiting in any way. It will be appreciated that modifications andalterations to the design, function or use of the heterogeneous reactorcore and fuel bundles may be made which are within the sphere of theinvention contemplated and are within the scope of the claims.

What is claimed is:
 1. A fuel bundle for use in a channel typeheterogeneous reactor core of a heavy water reactor, the fuel bundlecomprising: a central displacement tube; and a plurality of thoriumbased fuel pins surrounding the central displacement tube.
 2. The fuelbundle of claim 1, wherein the central displacement tube is filled withZrO₂, MgO, BeO, graphite or stagnant D₂O coolant.
 3. The fuel bundle ofclaim 1, wherein there are 21 radially positioned thorium based fuelpins surrounding the central displacement tube.
 4. The fuel bundle ofclaim 1, wherein there are 35 radially positioned thorium based fuelpins surrounding the central displacement tube.
 5. The fuel bundle ofclaim 1, wherein the fuel bundle is a seed fuel bundle and the pluralityof thorium based fuel pins comprises a homogeneous mixture of(PuO₂+ThO₂) with a PuO₂ content of 3% or higher.
 6. The fuel bundle ofclaim 1, wherein the fuel bundle is a seed fuel bundle and the pluralityof thorium based fuel pins comprises a homogeneous mixture of (UO₂+ThO₂)with a UO₂ content of 35% or higher.
 7. The fuel bundle of claim 1,wherein the fuel bundle is a blanket fuel bundle and the plurality ofthorium based fuel pins comprises a homogeneous mixture of (PuO₂+ThO₂)with a PuO₂ content of 2% or less.
 8. The fuel bundle of claim 1,wherein the fuel bundle is a blanket fuel bundle and the plurality ofthorium based fuel pins comprises a homogeneous mixture of (UO₂+ThO₂)with a UO₂ content of 30% or less.
 9. A method of using a thorium basedfuel comprising: placing the fuel bundle of claim 1 in a channel typeheterogenous reactor core of a heavy water reactor; and conducting aburnup of the thorium based fuel.